ML20057F326
| ML20057F326 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/06/1993 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20057F327 | List: |
| References | |
| NPF-68-A-069, NPF-81-A-048 NUDOCS 9310150144 | |
| Download: ML20057F326 (7) | |
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E UNITED STATES i
4i NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. NPF-68 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Gcorgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated July 31, 1992, as supplemented January 22 and July 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicabic requirements have been satisfied.
9310150144 931006-PDR ADOCK 05000424 P
3 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 69, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with j
the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1 h-MW I
4 avid B. Matthews, Director D
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Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: October 6, 1993 k
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UNITED STATES Q
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
- 6 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated July 31, 1992, as supplemented January 22 and July 27, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The fac.lity will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliancc with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
J..
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i 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 48, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
^A W 4 David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
October 6, 1993
1 ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 1
Add the following pages to the Appendix "A" Technical Specifications with the enclosed pages. These pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paoes Insert Paoes 3/4 7-9a B 3/4 7-2a
1 PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 Four main feedwater isolation valves (MFIVs), four main feedwater regulating valves (MFRVs), and associated bypass valves shall be OPERABLE.
APPLICABILITY:* MODES 1 AND 2, except when the MFIV, MFRV or associated bypass valve is closed and deactivated.
ACTION:
a.
With one MFIV, MFRV, or associated bypass valve inoperable in one or more feedwater lines, operation may continue provided each inoperable valve is restored to OPERABLE status or closed in each feedwater line within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Otherwise be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With no isolation system (each system consisting of a MFIV and its associated bypass valve or a MFRV and its associated bypass valve)
OPERABLE ** in any one feedwater line, restore at least one isola-tion system in each feedwater line to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.6(a) Each MFIV, BFIV, MFRV and BFRV shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.
The provisions of 4.0.4 are not applicable for entry into MODE 2.
4.7.1.6(b) For each inoperable valve, verify that it is closed or isolated once per 7 days.
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- Each MFIV, MFRV, or associated bypass valve shall be treated independently.
- An OPERABLE main feedwater isolation system may consist of inoperable valves provided the inoperable valves are maintained closed and deactivated.
V0GTLE UNITS - 1 & 2 3/4 7-9a Amendment No. 69 (Unit 1)
Amendment No. 48 (Unit 2)
PLANT SYSTEMS BASES 3/4.7.1.6 AUXItIARY FEEDWATER SYSTEM Isolation of the main feedwater (MFW) system is provided when required to mitigate the consequences of a steam line break, feedwater line break, feed-water controller malfunction, steam generator tube rupture or small break loss of coolant accident.
Redundant isolation capability is provided by two isola-tion systems on each steam line consisting of the main feedwater isolation valve (MFIV) and its associated bypass valve (BFIV) and the main feedwater regulating valve (MFRV) and its associated bypass valve (BFRV). The safety function of these valves is fulfilled when closed.
Therefore, a feedwater iso-lation system may be considered OPERABLE if its respective valves are OPERABLE or if they are maintained in a closed and deactivated position. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time to either restore or close an inoperable valve takes into account the redundancy afforded by the remaining OPERABLE valves and the low probability of an event occurring that would require isolation of the MFW flow paths during this time period.
The 7 day completion time to verify that an inoperable valve is closed or isolated is reasonable based on valve status indications available in the control room, and other administrative controls to ensure the valves are closed or isolated.
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L V0GTLE UNITS - 1 & 2 B 3/4 7-2a Amendment No. 69 (Unit 1)
Amendment No. 48 (Unit 2) j 1
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